ENTRY 11285 20241001 151511285000 1 SUBENT 11285001 20241001 151511285001 1 BIB 10 26 11285001 2 AUTHOR (E.A.Davis,T.W.Bonner,D.W.Worley JR,R.Bass) 11285001 3 TITLE Disintegration of O16 and C12 by fast neutrons 11285001 4 REFERENCE (J,NP,48,169,1963) 11285001 5 #doi:10.1016/0029-5582(63)90153-6 11285001 6 (W,DAVIS,1963) Tabulated data 11285001 7 INSTITUTE (1USARIC) 11285001 8 FACILITY (VDG,1USARIC) The Rice University 5.5 MeV Van de Graaff11285001 9 accelerator. 11285001 10 INC-SOURCE (D-D) Mono-energetic neutrons for studying the 11285001 11 reactions from 5.0-8.8 MeV were produced with the 11285001 12 D(d,n)He-3 reaction using a gas target. 11285001 13 INC-SPECT Energy resolution varies from 25 keV at 5.0 MeV to 50 11285001 14 keV at 8.5 MeV. 11285001 15 DETECTOR (IOCH,LONGC) Grid-type ionization chamber, and 11285001 16 neutron flux monitoring. 11285001 17 CORRECTION In the present experiment the wall loss for the alpha 11285001 18 particles from the O16(n,alpha0)C13 reaction varied 11285001 19 from 8 to 25 %. For the alpha particles from the 11285001 20 other reactions the loss was about 7 %. The analyzer 11285001 21 dead time varied from about 1 to 10%. 11285001 22 HISTORY (19761001T) Translated from SCISRS 11285001 23 (19810428A) converted to reaction formalism 11285001 24 (20150504A) BP: Updated to new date formats, lower 11285001 25 case. corrections according last EXFOR rules and 11285001 26 Dict., added doi and multiple corrections. 11285001 27 (20240915A) OS. STATUS modified in subs.2-5 11285001 28 ENDBIB 26 0 11285001 29 NOCOMMON 0 0 11285001 30 ENDSUBENT 29 0 1128500199999 SUBENT 11285002 20241001 151511285002 1 BIB 5 14 11285002 2 REACTION (6-C-12(N,A)4-BE-9,PAR,SIG) 11285002 3 METHOD (PHD) Excitation functions for the various reactions 11285002 4 in oxygen and carbon were obtained by analyzing 11285002 5 pulse-height distributions. 11285002 6 ERR-ANALYS (ERR-T) Total uncertainty 11285002 7 (ERR-S,1.,25.) Counting statistics and adding the 11285002 8 counts in each group of the pulse-height distribution. 11285002 9 (ERR-1) Determination of the absolute neutron flux 11285002 10 from the long counter measurements. 11285002 11 (ERR-2) Background corrections. 11285002 12 (ERR-3) Correction of each particle group for wall 11285002 13 loss. 11285002 14 STATUS (TABLE) Tabulated data received from Davis, 03/1963 11285002 15 HISTORY (20240915A) STATUS text updated 11285002 16 ENDBIB 14 0 11285002 17 COMMON 5 3 11285002 18 E-LVL ERR-T ERR-1 ERR-2 ERR-3 11285002 19 MEV PER-CENT PER-CENT PER-CENT PER-CENT 11285002 20 0. 35. 15.0 2.0 4.0 11285002 21 ENDCOMMON 3 0 11285002 22 DATA 2 13 11285002 23 EN DATA 11285002 24 MEV B 11285002 25 7.88 5.900E-02 11285002 26 7.92 6.500E-02 11285002 27 7.98 7.100E-02 11285002 28 8.03 7.700E-02 11285002 29 8.08 7.100E-02 11285002 30 8.13 7.100E-02 11285002 31 8.19 6.500E-02 11285002 32 8.24 6.100E-02 11285002 33 8.29 4.400E-02 11285002 34 8.34 4.200E-02 11285002 35 8.40 4.000E-02 11285002 36 8.45 3.600E-02 11285002 37 8.64 3.200E-02 11285002 38 ENDDATA 15 0 11285002 39 ENDSUBENT 38 0 1128500299999 SUBENT 11285003 20241001 151511285003 1 BIB 5 14 11285003 2 REACTION (8-O-16(N,A)6-C-13,PAR,SIG) 11285003 3 METHOD (PHD) Excitation functions for the various reactions 11285003 4 in oxygen and carbon were obtained by analyzing 11285003 5 pulse-height distributions. 11285003 6 ERR-ANALYS (ERR-T) Total uncertainty 11285003 7 (ERR-S,1.,25.) Counting statistics and adding the 11285003 8 counts in each group of the pulse-height distribution. 11285003 9 (ERR-1) Determination of the absolute neutron flux 11285003 10 from the long counter measurements. 11285003 11 (ERR-2) Background corrections. 11285003 12 (ERR-3) Correction of each particle group for wall 11285003 13 loss. 11285003 14 STATUS (TABLE) Tabulated data received from Davis, 03/1963 11285003 15 HISTORY (20240915A) STATUS text updated 11285003 16 ENDBIB 14 0 11285003 17 COMMON 6 3 11285003 18 E-LVL E-LVL ERR-T ERR-1 ERR-2 ERR-3 11285003 19 MEV MEV PER-CENT PER-CENT PER-CENT PER-CENT 11285003 20 3.68E+00 3.85E+00 50. 15.0 2.0 4.011285003 21 ENDCOMMON 3 0 11285003 22 DATA 2 8 11285003 23 EN DATA 11285003 24 MEV B 11285003 25 8.09 2.7E-02 11285003 26 8.16 2.7E-02 11285003 27 8.21 3.1E-02 11285003 28 8.26 2.3E-02 11285003 29 8.32 1.3E-02 11285003 30 8.37 1.5E-02 11285003 31 8.44 1.3E-02 11285003 32 8.64 9.E-03 11285003 33 ENDDATA 10 0 11285003 34 ENDSUBENT 33 0 1128500399999 SUBENT 11285004 20241001 151511285004 1 BIB 5 18 11285004 2 REACTION (8-O-16(N,A)6-C-13,PAR,SIG) 11285004 3 METHOD (PHD) Excitation functions for the various reactions 11285004 4 in oxygen and carbon were obtained by analyzing 11285004 5 pulse-height distributions. 11285004 6 ERR-ANALYS (ERR-T,20.,30.) Data error varies from about 20 11285004 7 percent at 5 MeV to about 30 percent at 8.7 MeV. 11285004 8 Error is considerably larger where cross section 11285004 9 becomes less than 10 mb. 11285004 10 (ERR-S,1.,25.) Counting statistics and adding the 11285004 11 counts in each group of the pulse-height distribution. 11285004 12 (ERR-1) Determination of the absolute neutron flux 11285004 13 from the long counter measurements. 11285004 14 (ERR-2) Background corrections. 11285004 15 (ERR-3) Correction of each particle group for wall 11285004 16 loss. 11285004 17 STATUS (TABLE) Tabulated data received from Davis, 03/1963 11285004 18 HISTORY (20150504A) BP: Corrected data set per IAEA's request. 11285004 19 (20240915A) STATUS text updated 11285004 20 ENDBIB 18 0 11285004 21 COMMON 4 3 11285004 22 E-LVL ERR-1 ERR-2 ERR-3 11285004 23 MEV PER-CENT PER-CENT PER-CENT 11285004 24 0. 15.0 2.0 4.0 11285004 25 ENDCOMMON 3 0 11285004 26 DATA 2 160 11285004 27 EN DATA 11285004 28 MEV B 11285004 29 5.02 0.13 11285004 30 5.03 0.141 11285004 31 5.05 0.15 11285004 32 5.07 0.14 11285004 33 5.08 0.127 11285004 34 5.09 0.113 11285004 35 5.11 0.108 11285004 36 5.12 0.11 11285004 37 5.13 8.80E-02 11285004 38 5.15 6.50E-02 11285004 39 5.16 4.30E-02 11285004 40 5.18 2.80E-02 11285004 41 5.20 1.60E-02 11285004 42 5.24 8.70E-03 11285004 43 5.28 4.70E-03 11285004 44 5.29 4.70E-03 11285004 45 5.31 8.50E-03 11285004 46 5.33 7.60E-03 11285004 47 5.35 1.40E-02 11285004 48 5.37 1.80E-02 11285004 49 5.39 1.40E-02 11285004 50 5.41 4.80E-03 11285004 51 5.56 2.80E-03 11285004 52 5.58 4.50E-03 11285004 53 5.60 3.60E-03 11285004 54 5.62 5.90E-03 11285004 55 5.64 7.90E-03 11285004 56 5.66 1.50E-02 11285004 57 5.68 1.90E-02 11285004 58 5.70 1.60E-02 11285004 59 5.72 9.20E-03 11285004 60 5.76 8.60E-03 11285004 61 5.84 1.1E-02 11285004 62 5.88 2.E-02 11285004 63 5.90 4.6E-02 11285004 64 5.92 8.E-02 11285004 65 5.94 6.5E-02 11285004 66 5.96 3.5E-02 11285004 67 6.00 1.4E-02 11285004 68 6.04 1.3E-02 11285004 69 6.06 3.6E-02 11285004 70 6.08 7.E-02 11285004 71 6.09 6.7E-02 11285004 72 6.10 5.3E-02 11285004 73 6.12 3.2E-02 11285004 74 6.14 3.1E-02 11285004 75 6.16 3.6E-02 11285004 76 6.20 4.2E-02 11285004 77 6.24 4.1E-02 11285004 78 6.29 3.7E-02 11285004 79 6.30 3.7E-02 11285004 80 6.33 4.4E-02 11285004 81 6.35 6.10E-02 11285004 82 6.37 9.80E-02 11285004 83 6.39 0.147 11285004 84 6.41 0.157 11285004 85 6.42 0.151 11285004 86 6.44 0.113 11285004 87 6.47 9.10E-02 11285004 88 6.49 8.20E-02 11285004 89 6.51 9.50E-02 11285004 90 6.53 0.112 11285004 91 6.54 0.131 11285004 92 6.57 0.14 11285004 93 6.60 0.137 11285004 94 6.62 0.126 11285004 95 6.63 0.116 11285004 96 6.65 0.101 11285004 97 6.68 9.30E-02 11285004 98 6.70 8.20E-02 11285004 99 6.72 7.20E-02 11285004 100 6.74 7.60E-02 11285004 101 6.77 8.70E-02 11285004 102 6.79 9.30E-02 11285004 103 6.81 0.106 11285004 104 6.82 0.104 11285004 105 6.83 9.80E-02 11285004 106 6.86 7.10E-02 11285004 107 6.88 5.80E-02 11285004 108 6.90 5.60E-02 11285004 109 6.92 5.70E-02 11285004 110 6.95 5.80E-02 11285004 111 6.97 5.80E-02 11285004 112 6.99 6.20E-02 11285004 113 7.01 7.20E-02 11285004 114 7.04 8.00E-02 11285004 115 7.06 7.40E-02 11285004 116 7.08 7.00E-02 11285004 117 7.11 7.50E-02 11285004 118 7.13 8.70E-02 11285004 119 7.15 0.111 11285004 120 7.16 0.135 11285004 121 7.18 0.159 11285004 122 7.20 0.206 11285004 123 7.22 0.19 11285004 124 7.24 0.147 11285004 125 7.25 0.132 11285004 126 7.27 0.11 11285004 127 7.28 8.40E-02 11285004 128 7.30 8.80E-02 11285004 129 7.33 9.10E-02 11285004 130 7.36 7.90E-02 11285004 131 7.39 7.40E-02 11285004 132 7.41 7.00E-02 11285004 133 7.44 6.60E-02 11285004 134 7.46 6.10E-02 11285004 135 7.48 6.00E-02 11285004 136 7.51 5.60E-02 11285004 137 7.53 5.60E-02 11285004 138 7.56 5.40E-02 11285004 139 7.58 5.90E-02 11285004 140 7.60 5.70E-02 11285004 141 7.63 4.90E-02 11285004 142 7.65 4.40E-02 11285004 143 7.68 4.00E-02 11285004 144 7.70 3.80E-02 11285004 145 7.73 3.60E-02 11285004 146 7.76 3.90E-02 11285004 147 7.78 4.30E-02 11285004 148 7.81 4.10E-02 11285004 149 7.83 4.20E-02 11285004 150 7.86 4.80E-02 11285004 151 7.88 5.00E-02 11285004 152 7.91 4.90E-02 11285004 153 7.93 5.10E-02 11285004 154 7.96 4.50E-02 11285004 155 7.99 4.00E-02 11285004 156 8.01 3.80E-02 11285004 157 8.04 3.80E-02 11285004 158 8.06 3.50E-02 11285004 159 8.09 3.70E-02 11285004 160 8.12 3.20E-02 11285004 161 8.14 3.40E-02 11285004 162 8.17 3.70E-02 11285004 163 8.20 3.90E-02 11285004 164 8.22 4.10E-02 11285004 165 8.25 3.80E-02 11285004 166 8.27 3.70E-02 11285004 167 8.30 3.20E-02 11285004 168 8.33 3.60E-02 11285004 169 8.35 3.60E-02 11285004 170 8.38 3.90E-02 11285004 171 8.41 3.70E-02 11285004 172 8.42 3.60E-02 11285004 173 8.44 3.40E-02 11285004 174 8.45 3.20E-02 11285004 175 8.48 2.90E-02 11285004 176 8.50 2.80E-02 11285004 177 8.53 3.30E-02 11285004 178 8.55 3.50E-02 11285004 179 8.58 3.90E-02 11285004 180 8.61 4.10E-02 11285004 181 8.62 4.30E-02 11285004 182 8.63 4.30E-02 11285004 183 8.65 4.60E-02 11285004 184 8.66 4.90E-02 11285004 185 8.69 4.60E-02 11285004 186 8.71 4.50E-02 11285004 187 8.74 4.40E-02 11285004 188 8.77 4.60E-02 11285004 189 ENDDATA 162 0 11285004 190 ENDSUBENT 189 0 1128500499999 SUBENT 11285005 20241001 151511285005 1 BIB 5 14 11285005 2 REACTION (8-O-16(N,A)6-C-13,PAR,SIG) 11285005 3 METHOD (PHD) Excitation functions for the various reactions 11285005 4 in oxygen and carbon were obtained by analyzing 11285005 5 pulse-height distributions. 11285005 6 ERR-ANALYS (ERR-T) Total uncertainty 11285005 7 (ERR-S,1.,25.) Counting statistics and adding the 11285005 8 counts in each group of the pulse-height distribution. 11285005 9 (ERR-1) Determination of the absolute neutron flux 11285005 10 from the long counter measurements. 11285005 11 (ERR-2) Background corrections. 11285005 12 (ERR-3) Correction of each particle group for wall 11285005 13 loss. 11285005 14 STATUS (TABLE) Tabulated data received from Davis, 03/1963 11285005 15 HISTORY (20240915A) STATUS text updated 11285005 16 ENDBIB 14 0 11285005 17 COMMON 5 3 11285005 18 E-LVL ERR-T ERR-1 ERR-2 ERR-3 11285005 19 MEV PER-CENT PER-CENT PER-CENT PER-CENT 11285005 20 3.09 35. 15.0 2.0 4.0 11285005 21 ENDCOMMON 3 0 11285005 22 DATA 2 18 11285005 23 EN DATA 11285005 24 MEV B 11285005 25 7.62 3.40E-03 11285005 26 7.67 3.40E-03 11285005 27 7.72 5.20E-03 11285005 28 7.77 2.80E-03 11285005 29 7.82 6.30E-03 11285005 30 7.87 5.80E-03 11285005 31 7.92 9.00E-03 11285005 32 7.98 9.70E-01 11285005 33 8.03 9.40E-03 11285005 34 8.08 9.80E-03 11285005 35 8.13 8.40E-03 11285005 36 8.19 8.20E-03 11285005 37 8.24 9.60E-03 11285005 38 8.29 8.30E-03 11285005 39 8.34 9.60E-03 11285005 40 8.40 1.02E-02 11285005 41 8.45 1.15E-02 11285005 42 8.64 1.17E-02 11285005 43 ENDDATA 20 0 11285005 44 ENDSUBENT 43 0 1128500599999 SUBENT 11285006 20150504 140711285 6 1 BIB 2 3 11285 6 2 REACTION 1(8-O-16(N,0),,EN) 11285 6 3 2(8-O-16(N,A),,WID) 11285 6 4 STATUS (TABLE) Table I, page 174. 11285 6 5 ENDBIB 3 0 11285 6 6 NOCOMMON 0 0 11285 6 7 DATA 3 19 11285 6 8 DATA 1DATA 2DATA-APRX 2 11285 6 9 MEV KEV KEV 11285 6 10 5.05 91. 11285 6 11 5.12 30. 11285 6 12 5.32 24. 11285 6 13 5.37 52. 11285 6 14 5.68 56. 11285 6 15 5.92 51. 11285 6 16 6.08 28. 11285 6 17 6.22 143. 11285 6 18 6.41 81. 11285 6 19 6.59 148. 11285 6 20 6.81 79. 11285 6 21 7.04 69. 11285 6 22 7.20 79. 11285 6 23 7.32 57. 11285 6 24 7.59 78. 11285 6 25 7.90 126. 11285 6 26 8.22 125. 11285 6 27 8.38 125. 11285 6 28 8.66 11285 6 29 ENDDATA 21 0 11285 6 30 ENDSUBENT 29 0 11285 699999 ENDENTRY 6 0 1128599999999